ML18047A614
| ML18047A614 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 10/13/1982 |
| From: | Toner K CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0820, RTR-NUREG-820, TASK-03-06, TASK-3-6, TASK-RR NUDOCS 8210190535 | |
| Download: ML18047A614 (51) | |
Text
{{#Wiki_filter:" consumers Power company General Offices: 1945 West Parnall Road, Jackson, Ml 49201 * (517) 788-0550 October 13, 1982 Dennis M Crutchfield, Chief Operating Reactors Branch No 5 Nuclear Reactor Regulation US Nuclear Regulatory Commission Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - SEP TOPIC III-6, SEISMIC DESIGN CONSIDERATIONS The attached enclosure provides a summary of the actions taken to date by Consumers Power Company to address specific NRC concerns as documented in the April 12, 1982 draft of NUREG-0820 regarding eccentric loads and valve functionability in small bore piping. Also summarized are Consumers Pow~r Company plans to perform additional analysis on control valve CV-3003 piping to more accurately assess pipe stress. It is the opinion of Cons'_uners Power Company that this enclosure adequately responds to the above stateJ NRC concerns.
~~arV~ ,/
Kerry A Toner Senior Licensing Engineer CC Administrator, Region III, USNRC NRC Resident Inspector - Palisades Enclosure 8210190535 821013 PDR ADOCK 05000255 p PDR
A
- ENCLOSURE
- CONSUMERS POWER COMPANY PALISADES SEP TOPIC III-6 Evaluation Of Valve Operator Eccentric Loads And Functionability In Small Bore Piping This is a summary of the actions ta.ken by Consumers Power Company to resolve NRC concerns about valve operator eccentric loads and valve functionability during seismic conditions in piping 2-inch and smaller.
A list of all Q-listed, 2-inch and smaller air operated control valves and motor operated valves was made up from the Palisades equipment data base. This list was then reduced by eliminating valves in non-critical services and valves without significant operator weight. Critical services were defined to be: 1) valves forming pa.rt of the primary coolant system boundary, 2) valves affecting the ability to maintain a stable shutdown condition (i.e., decay heat removal, reactivity control, primary coolant system inventory control), 3) valves required for emergency core cooling system function and
- 4) valves required for containment isolation. The result.was a total of 62 valves to be considered for evaluation of eccentric loads.
The majority of these valves are 1-inch and 2-inch control valves and 2-inch motor operated valves. There are also two 3/4-inch control valves and five 1/2-inch control valves on the list. The five 1/2-inch control valves are primary coolant sample system valves . The pipe s*bresses resulting from valve operator eccentric loads were evaluated on a sample basis and by review of some of the work done under IE Bulletin 79-14. The piping systems associated with three 2-inch control valves and one 1-inch control valve were analyzed as part of the 79-14 work. In these analyses the operators were modeled as eccentric masses and deadweight thermal and seismic loadings were included. One of the three 2-inch control valves (PCV-2164) is installed with its operator in the horizontal position and with a support on the operator itself. This is not typical of other control valves at Palisades so no conclusions were drawn from the analysis of.this valve. The other two 2-inch control valves (CV-2130 and CV-2136) are installed with their operators in the vertical position and with no supports attached to the operators. Pipe span lengths from these valves to the nearest supports are typical of other 2-inch control valves in the Palisades Plant. The 79-14 analysis showed the piping to be acceptable without addition of supports to the valve operators or any other modifications due to valve operator eccentric loads. Similarly, the analysis of the piping to 1-inch control valve CV-2153 showed the piping stresses to be within FSAR limits without the addition of any supports to the piping or the valve. Analyses of three additional valves were performed to confirm that 2-inch motor operated valves are adequately supported and to obtain more data on the piping to air operated control valves. Calculation summaries a.re attached (see Attachment #1). The analyses were done in accordance with FSAR requirements considering pressure, deadweight and seismic loadings. The valves to be analyzed were chosen based on piping spans between the valve and the nearest
- supports. Maximum span lengths were chosen since this would likely result in the highest pipe stresses. The results show that valve M0-3072 and CV-0438B are supported adequately.
Palisades Plant 2
- Enclosure - SEP Topic III-6 October 13, 1982 Since M0-3072 is of the same design as the other 2-inch motor operated valves, all of these valves can be considered to be adequately supported. The analysis of CV-0438B along, with the 79-14 analyses of the 2-inch control valves as discussed above,demonstrates adequate support for the 2-inch air operated control valves.
The third analysis, on 1-inch control valve CV-3003, was not completed because of lack of information on piping support locations. A section of the piping was modeled as unsupported because support locations were not known. As a result the piping was overstressed. It is expected that the actual support arrangement would result in stresses within allowable limits at the valve. This piping is inaccessible during plant operation, so the actual support locations have not been determined. During the next refueling outage, the supports will be located and CV-3003 pipe stress will be determined. Any overstress will be reported to the NRC. In SUillillary, analysis of seven Palisades piping systems containing 2-inch motor operated valves and 1-inch and 2-inch control valves has shown no overstresses resulting from valve operator eccentric loads except in one case where there was insufficient information on support locations. These analyses included limiting cases in terms of operator weights and piping span lengths. Based on these results, we believe that there is no pipe stress problem at Pali_sades associated with valve operator eccentric loads in small bore piping . The second NRC concern relative to eccentric loads in small bore piping is valve functionability. In this regard, we are enclosing two analysis reports (see Attachments 2 and 3) on stresses in 1-inch and 2-inch control valves due to seismic loadings. In both reports the seismic stresses are quite low, indicating that valve function would not be impaired by accelera-tions up to 3.0 g's. Based on these reports, we believe that air operated control valves will function during and after a seismic event. Although functionability of the 2-inch motor operated valves has not been analyzed specifically for this SEP Topic, Consumers Power Company does not expect that such valves will fail to function during a seismic event. This expectation primarily results from the analyses performed on the 1-inch and 2-inch control valves. The results of such analyses provide an indication of procurement and design practices which were generally employed during initial construction and subsequent modification of the Plant. Any further function-ability evaluation at this time is unwarranted since functionability e.s an issue is being evaluated generically by the NRC as part of Unresolved Safety Issue No. A-46, Seismic Qualification of Equipment In Operating Plants. The results of the NRC evaluation will be to establish an explicit set of guidelines that could be used to judge the adequacy of the seismic qualification of mechanical and electrical equipment at all operating plants (ie, equipment required to safely shutdown the plant and equipment whose function is not required for safe shutdown but whose failure could result in adverse conditions which might impair shutdown functions) and to requalify equipment whose seismic qualifi-cation is found to be inadequate .
I/ ATTACHMENT #1 Consumers Power Company PALISADES SEP TOPIC III-6 October 13, 1982
- 22 Pages
I ;
- Bechtel Associates Professional Corporation 777 East Eisenhower Parkway Ann Arbor, Michigan Mail Address: P.O. Box 1000, Ann Arbor, Michigan 48106 September 16, 1982 Mr. A. K. Smith Consumers Power Company 1945 west Parnall Road Jackson, Michigan 49201 Consumers Power Company Palisades Plant cPco.::Gwo..;.9551 **
Bechtel Job 12447-060 ECCENTRIC PIPE LOADS IN SMALL BORE (2n & SMALLER) PIPING File: 0275 82-12447/060-07
Reference:
AKR 11-82, dated July 29, 1982
Dear Mr. Smith:
Consumers Power Company requested Bechtel to perform a computer pipe stress analysis on three small bore (2n & smaller) piping systems as part of their SEP program with regard to eccentric loads. Bechtel's analysis of stress packages (S/N) 318, (S/N) 337 & (S/N) 320 include4 pressure, dead weight, and seismic effects only, in accordance with Appendix A of the FSAR. Computer program number ME101 was used in the performance of this request and the results are as follows:
- 1. S/N 318 Valve M0-3072 is determined to be supported adequately to meet acceleration limits and stress allowables in Appendix A of the FSAR. valve acceleration does not exceed 3g's. Pipe stresses in the vicinity of the valve are acceptable based on assumptions and valve data listed in the calculation summary (attached) and walkdown information related to piping configuration per drawings 12447-033-SP-FSK-CC-7-2, 3, 4, 5, 6, & 7 .
Bechtel Associates Professional Corporation Mr. smith, September 16, 1982 Page 2. S/N 337 valve CV-04388 is adequately supported and stresses meet FSAR allowables. Valve acceleration is less than 3g's. Stresses in the vicinity of the valve are acceptable based on assumptions and valve data listed in the calculation summary (attached) and walkdown information related to piping configuration per
. -drawings- 1244 7-033-SP-HCC-10 2 -& SP-HBC-31*-l ~
- 3. S/N 320 Valve CV-3003 is located in a piping system which involves ten isometrics. Additionally, a portion of the pipe was not verified during walkdown because it was deemed inaccessibte. The model for this analysis includes only a portion of the ten isometrics (piping beyond the model limits would not ~ave a significant effect on pipe stresses near CV-3003), however, the model does include the piping which was not verified. The piping not verified was assumed to be unsuppbrted which is a conservative assumption. The resulting analysis shows calculated stresses in the immediate area of the valve do not meet the FSAR allowable stresses. we note that if the inaccessible portion of the piping is found to be adequately supported, the stress levels are expected to drop sufficiently in the area of valve CV-3003 and associated piping to permit an acceptable condition without the need for any modifications.
If you have any questions, please advise. ' Very truly yours(- *.,_< 4:).~~A_/) P-: K. smith .
£/Project Engineer TP/PKS/lah Enclosure
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PREPARATION INSTRUCTIONS
.1 . ORIGINATOR RESPONSIBILITIES Complete all title blocks with the following information: project, job number (include subjob), discipline. calculation number. revision, originator (include full name of all originators)." date originated, total number of sheets compris-ing the summary (enter on cover sheet only}, and pagination of all sheets excluding cover sheet.
- b. Complete all summary sheets appropriately to include all assumptions, methods used (e.g., computer program and revision, etc), design input, results, and conclusions.
- c. Complete cover sheet revision block with revision, description, and originator's initials and date.
- 2. CHECKER RESPONSIBILITIES
- a. Check the summary against the calculation to verify completeness and adequacy. (Checker cannot be the originator.) *
' b. Initial and date all pages including the cover sheet.
- c. Initial and date cover sheet revision blod<.
- 3. REVIEW ANO APPROVAL
- a. The discipline group supervisor or designee reviews for completeness and initials and dates the cover sheet revi-sion biock to indicate concurrence .
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CALCULATION
SUMMARY
PREPARATION INSTRUCTIONS Complete all title blocks with the following information: project, job number (include subjob). discipline. calculation number, revision, originator (include full name of all originators), date originated, total number of sheets compris-ing the summary (enter on cover sheet only), and pagination of all sheets excluding cover sheet. *
- b. Complete* all summary sheets appropriately to include all assumptions, methods used (e.g., computer program and revision, etc), design input, results. and conclusions.
- c. Complete cover sheet revision block with revision, description, and originator's initials and date.
- 2. CHECKER RESPONSIBILITIES
- a. Check the summary against the calculation to verify completeness and adequacy. (Checker cannot be the originator.)
- b. Initial and date all pages including the cover sheet.
- c. Initial and date cover sheet revision block.
- 3. REVIEW AND APPROVAL
- a. The discipline group supervisor or designee reviews for completeness and initials and dates the cover sheet revi-sion block to indicate concurrence. *
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SHEET 12447 c:::-os:-o.:**,~
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ATTACHMENT #2 Consumers Power Company PALISADES SE~ TOPIC III-6 October 13, 1982
- 16 Pages
e HENR~<<>~-t_ P.0. Box 1918 -- 502. 634-9411 MACHINE C-Louisville, Ky. 40201 ENGINEERING DEPARTMENT CRO 157907 coMPANY _ _B_e_c_h_t_e_l_C_o_r.... p_o_r_a_t_i_o_n_ _ _ _ _ _ _ _ _ _ _ _ _ __ JOBNO. 5935-M336-AC ADDRESs _ _P_._o_._B_o_x_3_9_6_5-'-,_s_a_n __ F_r_a_n_c_i_s_c_o'"'"',_c_a_l_i_*f_o_r_n_i_a_ _ _ _ _ _ _ _ _ _ _ _ __ su~ECT _ __,!s~e~i~*s~mw..ai~c_......Awn~a~l~y~s~i~s.._-_B_e_c_h_t_e_l_I_t_e_rn_l_S_._1_____~2~--,.:..*-----------
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*I 413;...1-~- -spring: return; size--* 40 side mounted-tylindelj'- hi:mqwhf=el -- ----
---- and asso.ciated __ .equipmentl....for. opez:a.tion. ! Thel totatl._ wei9:h.1;_oif the.~
1 I r Fisher IcyliJ?-der operator! i~ 7~# ~ The approxd.rnatel w~igpt !ofl trte I ;
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j f!ll~l__ _ _ i__ j '. 1 , 1 1 1 1 l 1 I 1 1 , * . , ASSQM-;;~oNs~---PROC~-;~~~sl__*_:- i *. ,_~]_ *- ~§ f ' I I I * ! ! I _L_Ll. ~ '.l'wq _si=ismic_c;_on:;;iq~:t~ODLCiret COVS!J::_eQ. bi_j;_be:_ c~,l.-~~l_q.ti_Qn.._s as_ ; .
' I I t~~-lo~s 1- ! __Lj __ J_j_ __ j __ l j_l__ j -L--~-~- [_l___ L_ ;____* _'._ .:__i_L_ _
j--- i ___ J -- ___ ____ ,__ , __ j\. 1 __ A:_complete__ ~efsmic_'.an~lysi~ of_ ~he _vk1~eL.bpJra~o~ ___w~e~ __l __ I Loperating at a 3g horizontal and vertical! acceleratP,.on. ! ' 1 -f-- - _- H I l-~=- J=-triihe:~-~naryiisl~j af~j~_~fd i ~~-L~LD~1-~~~~11:~~ ~~~l~~~~-;-~ B. I An analysis! on the 'valve bonneti as ai resu!l.t lofl the increased
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~ - -- . . : Calculation.s indicate; that valve and_ operato:r shou14__Q£_ei;-_a"j:.~_l_ _j_
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~""ISIIEI~ CONTI~OLS CO~IPANY MARSHALLTOWN, IOWA 50158.
AUTOMATIC CONTROL EQUIPMENT SINCll 1111110 September 27, 1973
- Seismic Certification for:
Agent Order: 50-2088
.. -.* Customer Order: c~40934 Serial No. Tag No.
5655387 CV-0437A *::;--:* .. ;,: 5655388 CV-0437B 5655389 CV-0438A 5655390 CV-0438B Enclosed is the seismic calculations for a s*ize 40 Type 473-1-5 piston actuator. *The equipment is considered to be .able to withstand the specific seismic distl,lrbance i f the calculated stress does not exceed 50% of the tensile stress of cast iron and does not exceed the stress at room temperature of the yoke locknut. Yoke Cast Iron; ASTM A48-Class 30 50% of the Tensile Stress = 15000 PSI Yoke Locknut Steel, ASTM A235 - Class A Approximate Yield in Shear = 20000 PSI Also enclosed is a seismic test of an Asco solenoid performed by the Research Department. This is in compliance with the specifications _ levied on accessories. L~-"" Dave Howells Project Engineer DH:dn - encl. Ir
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FISHER coN~RoLs . corv1P!Jv' Project 7JAR4.3 MARSHALLTOWN, IOWA PROB. ___ 15_2_9_ _ _ _ __
. **.. - REPORT _ __._14_ . _ _ _ __
. *** PAGE _____1_____________
*. OATE _____5_-9_-_7_3_________
. ,... LABORATORY REPORT VIBP.A noN TEST OF ASCO SOLENOID VALVE" Imt Solenoid Valve lYPE 3-Ylay Universal 11.ANUFACllJRER Autor.ia tic Switch Company DESIQl - - - - - - - - - - - -
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- SIZE 1/4 NPT DWG SP~IAL. 1D~n_IFICAT!etl C-at.a~~5% HT 8320A107 - SN 958725 7 .
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PURPOSE* Vibration tests were conducted to generate data for customers who require seismic infolllliltion *
- TEST PROCEDURE*
TYPE OF MJUNTING& See attached copy of Test Procedure.*
*~ ...
The assembly was nipple mounted "!:hru a bracket moul)ted to the shaker table.
- ACCEI.ERCMETER l.OCA.TIONa The accelerometer was mounted on the shaker table.
RESULTS& DIRECrICN 1 . - No Ma !function DIRECI'_IOO 2 - No Malfunction
- DIRECI100
. . 3 - No Malfunction NOTEs See Data Sheets 1 and 2 for illustration of directions.
OO~CLUSICX~S AND RECOl.MB~Dr\TICl~SI The ASCO Solenoid Valve perfonned satisfactorily
*and meets or exceeds the. specification outlined in the Test Procedure.
GJ. m. u)_jj~
~ames M. Wilkinson
- Research Department
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ATTACHMENT #3 Consumers Power Company PALISADES SEP TOPIC III-6 October 13, 1982 1 Pages
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5e _*-~.:S49~ * .'... PSI_ .. sJ_~f.S.L___ z.5.PQ.o._: __p_s1_ __ .... STR~ss____ , set. J _1503, .. Psr _____ ,_ ,sTRfss ... :15000*. 1~Ps1..:. ...* L....:. ____ .;.~-~- 1 ;;;_ STR<SS __ 1 Jsi :*~ <:.*~:~::* *:*. ~':~~~:-.': ~ *.'.Jl? ~
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* *-**....** ....:.* *. - . TOTAL YOl(f *LLOWABlE * - * .,
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-; . *- - . , ;; . . STPF.S S
- SYT ) 213'.-. PS STRFSS .:- 17500.
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-.~-Li CRK ORDfR N~.~BBJ66-JJl .. ... *.**10 SIZF. 't.OOl'jCll TYPF .t,OJl l RATING kOC* LBS. ACTUATOR 18 .5P DES IG'4 PRES.SURE 750. PSIG
-...---- -- ---** - .. _. _, i BODY GSKT O.O.
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- 6.t,t,Q 5.f.5C 1111.
lN* BON*~ET r. INPUT DATA
.1.CTUATf1R WlnTH (l!~.
WGT
- 260.000 4.500 LBS.
l'I.
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H l=AC:T OR 3.JJQ ACTUATnP 11r;T. 305.0JO LBS. £1UlSIClE OIM. 7.670 IN. ' (' Y FACTOR 4500.00C PRESS. 13.000 PSI INSIDE 0111. 6.120 !'I. !0 SEAT GSKT O.O. 5.62C IN. n1Al>HRllG,.. AHA 27b.OOO SO.JN. C.G. HEIGHT 16.000. l'-1. ..... .. i j
- 1. o.
M FACTOP Y FACTOR 4500.000 4.f.20 3.000 l"d. C.G. HEIGHT HUR o.o. 17.380 3.000 IN. ltl. OESlrN STRESS l!ONN'l ~ 60F INTfNSITV 17500. PSI iii TEMP p5oq. PSI _________ , ....... -..... ______ ;: I:
- 'It YO~F ~ 60F FLANGE O.!l.
1.0. B.c. 9.620 1.7-50 7.BBC llJ. l'l.
.JN.
ACCFLERATION VfPTICAL H(lRIZOr-;TAL 3.000 r.. 3.000. G. BOLT <l 60F NUT ii: 60F 17500. PSI 25000. PSI ii TEMP 20000. __ PSI_ .. 25000. PSI .. *. . : Ji ;. THICKlllF.SS 1.593 IN. --*- -~ .......... - - - ' " - - :
- j 1---.'£'
BOLT SIZE 0.875 IN. ~;UT SHR AREA/IN. 7.302 SQ. IN./IN. t;xTFRNAl M011FNT 0.0 I'll-LBS 1. * ** QUANT ITV .. e.ooo F.NGAGfMFNT **--*'- 0.625 ti>. !! F:JRCE o.o . .-* LBS.;- . -**---- * - - - - - - - * - * - - - - - - *
- _ _ ""' i I :;i~.
VALVE 801)V JO. 4.0JO _l'-1. lllAMfTER 3.312 IN. , PPFSSURE FD 750.000 PSIG . . . . . . . , .. , .. 1** ~i:
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HAND WHEEL 1110. 1 WHl HOl 31l392. 61715. NORMAL FL ANGE
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- . i' STRESSfS SH 5777. PSI STPESSES 26250. PSI . ,.STP~SSFS Sf'T **** u1el.--PSI *.. STRESSEs 52500.: PSI --'.-*~-~-c...;------*j*i ;.;.
STT~ OPfRATl~*G SH'I ST SR
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8208. 8't20.
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PSI PSI 17500.
. 17500.
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PSI PSI ~~;r:~g SflT 12056. PSI 12367 *.
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PSI 52500. PSI . . ' '. .
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*52500.' PSI
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. * :- .ALLOWABLf ,,; . . I',:'. * * :* .. ; .'.:* ;, *. ** :;~:' *j .~
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. HlOWABlf .. : .* .: TOTAL FUNGf *:
NORMAL Fl A'4GE STRESSES SH *5529. PSI' stRe'sses**-*2r.z5a~* *Psi"*~** *nPESSFS *s..,r: 1291s.-*-*pn~"'~s*T1fEsse$.. ~52sop. "ps*1*""'7:--~T,-7j~'. ST 7856. PS!'. 17500. *PSI .. . STT 11704.'. .PSI-. . * *, ..* 52500. PSI .. * \ . } , ;_.:* *~.],'* A~~ . . =~::: .:~: .. '. . ---"; -~~ -- g~gg: .'.. ~~: ~- :. _'. *. . .... S~RT, ~~~; . g~~~= -::~: _:,:::-~ .:. -~-:*'.-*. ~~~f** :~~gg.::. -:~: -~(.:.:.:~}=..;... ;~~~~ 1* GASKET t : ~0M:-'---x:-.:. i; :i :.;r!~ SHR A~*~ .. *-.. ~~-~~-2.* ..._~-~'. ___ -~ -~~--~5~~-.:*~~t. *::. ~ :.:.:_.* .:. ~~T-~ -~; i .:. :~ J: 1 Sill i, * <<
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---+- AVG 12320 ... PS I ... * . .. . 52501). PSI , : ... '.:'
NORMAL BOLT "',,.," , . . ,,. " *'" .* STRESS. SB ..* l06ZZ .... P s 1 ' ... *~ SJ!!~ ss ___2,5Q<,>O. ,......P~.~-- . St!FSS . : : ; li B~. : lP~~~-~f~)-~~ .;; : STRESS:. -~J50op*:. JS.t_*.:.;;.: 1' _\ .* t *;_ :;.*;* *. J!;; :;;~'. ;
. ........ _. ______ .. ___ ., . ,_. ,JOTAL T0KF * .. * . . * : ..*--- .. -~~~U,bllABLf I*- . . . . . . . . . ._,,. __.. '*;~~"!'. '."':)"
- ., . i ..... ~- .... _ ,__ ........... ; *-.~ >.. ._ STllfSS .,:, SYT, , 26'11 ... PSJ,; _ _. !iTRfSS:<*. ,l,500.*. ~.SI:,:..! .... :.:~--' _,_'..,.o. ..... ,;,:cJ,c ~1-,i
_*: --*~<< ,;'.~ ___ ... ________' ~------ * : TM Al NUT . ' ' "I:* *
.. , ~:-srRtss *-**.r-:ur'T *" 'i:fu;*.-- * . ALLOWABLE .*!* J' .
isr-::-.* ,*srRds ~-~ 20001t~- Pst'-::-::;---' ** *,..
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